#TITLE_ALTERNATIVE#

• Main Author: WIJAYA (NIM : 10212010), LEO
• Format: Final Project
• Language: Indonesia
• Online Access: https://digilib.itb.ac.id/gdl/view/22885
• Institution: Institut Teknologi Bandung

Pressurized Water Reactor is the most used reactor in the world. This reactor uses thermal neutron to activate nuclear fission chain reaction to generate heat that will be conversed to electrical power. One of the problems in PWR design is the spent fuel management procedure after the reactor stops working to produce heat (shutdown). The spent fuel contains radioactive nuclides that have long life. But few of them can be used as fresh fuel in reactor core, such as uranium and plutonium. Nevertheless, the spent fuel must be reprocessed to extract uranium and plutonium together with minor actinides (MA) and other fission product. This process is known as partitioning stage. Partitioning process is high-priced and only a few of countries are allowed to have reprocessing plant. Thus, the SUPEL scenario process can be the alternative solution. Straight Utilization of Spent LWR Fuel in LWR System is direct cycling process of spent fuel and treated as fresh fuel in reactor core. The spent fuel directly inserted to a new fuel rod after stored in temporary pool for five years without partitioning stage and reprocessing stage. The advanced evaluation of SUPEL scenario is counted by SRAC2006 program which uses JENDL3.3 library nuclear data on Westinghouse PWR 3411MWt. The SRAC2006 calculation shows enrichment 4.6% uranium 235 and boric acid 15000ppm can obtain criticality of PWR 3411MWt for three years. Boric acid is depleted till 300 days and obtain small reactivity swing. The total amount of nuclides in spent fuel are 111 nuclides with different amount of atomic density each others in the end of reactor operation. All of this data will be used for the SUPEL calculation by SRAC2006, then show enrichment 5% of uranium 235 can obtain criticality for three years for maximum 9% amount of spent fuel. Besides, enrichment 4.6% of uranium 235 can obtain criticality for three years just with 1.5% of spent fuel. Calculation shows that high amount of spent fuel need high enrichment of uranium also to obtain criticality.